有机工质反应堆燃料组件物理计算及堆芯设计

doi:10.11896/cldb.20070337

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摘要有机工质堆芯因其特有的优势可用于移动核动力反应堆。本工作在以三联苯(C₁₈H₁₄)为冷却剂和慢化剂的基础上,设计石墨慢化的有机工质反应堆(ONR)堆芯燃料组件,采用蒙特卡罗程序研究了石墨棒束对组件物理特性的影响,并分析了ONR组件的反应性控制特性。计算得到不同石墨棒数下ONR燃料组件中子能谱、每次裂变平均释放的能量、每次裂变释放的中子数、组件相对释放能量、k_eff、功率峰因子、冷却剂和石墨中能量沉积份额,以及可燃毒物和控制棒的微分价值。研究结果对ONR堆芯功率的设计和优化有一定的参考价值。

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	王锋
	孙源楠
	苏兴康

关键词: 有机工质反应堆燃料组件石墨慢化蒙特卡罗方法物理特性

Abstract: Organic nuclear reactor core is advantageous for mobile nuclear power applications. In this study, based on the design of C₁₈H₁₄ as both coolant and moderator, novel design of graphite moderated, C₁₈H₁₄ cooled organic working medium reactor(ONR)core and fuel assembly was carried out. Monte Carlo code was used to study physical properties with different numbers of graphite rod, and fuel assembly control was also analyzed. Neutron characteristic results of neutron spectrum, energy release, the number of total neutrons per fission, percent energy deposition on the coolant and graphite under different numbers of graphite, k_eff, and relative peak power were obtained. And the fuel assembly perfor-mance including differential value of burnable poison and control rod were also acquired. These results can be used as reference for the design of the ONR power and optimization.

Key words: organic nuclear reactor fuel assembly graphite moderated Monte Carlo method physical characteristics

出版日期: 2021-09-25 发布日期: 2021-09-30

ZTFLH:

TL349

基金资助: 核反应堆系统设计技术重点实验室基金项目(JG2018119);重庆市技术创新与应用示范(产业类重点研发)基金项目(CSTC2018JSZX-CYZDX0100)

作者简介: 王锋,重庆大学副教授,硕士研究生导师。2001年本科毕业于重庆大学热能工程专业,获工学学士学位;2008年博士毕业于重庆大学工程热物理专业,获工学博士学位。2010年评为副教授。2013—2014年在美国佛罗里达国际大学机械与材料工程系做访问学者。中国可再生能源学会、中国核学会、中国化工学会、重庆市能源研究会等会员,重庆市大学科学传播研究会第三届理事会理事。Journal of Materials Science & Technology, Materials Letters, ACS Applied Nano Materials等学术期刊审稿人。研究方向包括传热传质、冷喷涂、核能与氢能中的热物理问题等。

引用本文:

王锋, 孙源楠, 苏兴康. 有机工质反应堆燃料组件物理计算及堆芯设计[J]. 材料导报, 2021, 35(18): 18195-18199.
WANG Feng, SUN Yuannan, SU Xingkang. Novel Organic Nuclear Reactor Fuel Assembly Physical Calculation and Reactor Core Design. Materials Reports, 2021, 35(18): 18195-18199.

链接本文:

http://www.mater-rep.com/CN/10.11896/cldb.20070337 或 http://www.mater-rep.com/CN/Y2021/V35/I18/18195

1 Huang H, Xu M. Nuclear Power Engineering, 1995, 16(5), 401 (in Chinese).
黄海, 徐明. 核动力工程, 1995, 16(5),401.
2 Ma J, Li L J, Huang Y P, et al. Nuclear Power Engineering, 2011, 32(2), 91 (in Chinese).
马建, 李隆键, 黄彦平, 等. 核动力工程, 2011, 32(2), 91.
3 Shirvan K, Kazimi M. Nuclear Engineering & Technology, 2016, 48(6), 1338.
4 Sheng H Y. Atomic Energy Science and Technology, 1962, 4(4), 277 (in Chinese).
盛怀禹. 原子能科学技术, 1962, 4(4), 277.
5 Zhang M W. Chinese Science Bulletin, 1961(12), 18 (in Chinese).
张曼维. 科学通报, 1961(12),18.
6 Zhang D W. Chemistry(Huaxue Tongbao), 1959(12), 29 (in Chinese).
张定武. 化学通报, 1959(12), 29.
7 Polushkin K K, Emel'Yanov I Y, Delens P A, et al. Atomic Energy, 1964, 17(6), 1197.
8 Weeks J L. Arch Environ Health, 1971, 23(2), 123.
9 Shirvan K, Forrest E. Nuclear Engineering & Technology, 2016, 48(4), 893.
10 He K Y, Han W S. Nuclear Power Engineering, 2007, 28(4), 9 (in Chinese).
贺克羽,韩伟实. 核动力工程, 2007, 28(4), 9.